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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Hubertus Nickel, Florian Schubert
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 649-660
H. Design Codes and Life Prediction | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33486
Articles are hosted by Taylor and Francis Online.
Based on the existing structural design code for pressure vessel and nuclear light water reactor power stations, situations for metallic structures in hightemperature gas-cooled reactors (HTGRs) are described for those metallic structures that mainly operate in temperature ranges of time-independent and time-dependent materials properties. The ASME Code Case N 47 is critically reviewed. For advanced HTGRs with components for operating temperatures >800°C, no nuclear accepted structural design code exists. The status of the ongoing work for the basis of those codes is given with the main emphasis on the situation in the Federal Republic of Germany.
